KR930017045A - Nuclear fuel rods and cladding manufacturing method of such fuel rods - Google Patents

Nuclear fuel rods and cladding manufacturing method of such fuel rods Download PDF

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KR930017045A
KR930017045A KR1019930000501A KR930000501A KR930017045A KR 930017045 A KR930017045 A KR 930017045A KR 1019930000501 A KR1019930000501 A KR 1019930000501A KR 930000501 A KR930000501 A KR 930000501A KR 930017045 A KR930017045 A KR 930017045A
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iron
zirconium
chromium
weight
cladding
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KR1019930000501A
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Korean (ko)
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뽈 마르동 장
쎄네바 장
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프라마똠
지르꼬티브
원본 미기재
꽁파니 제네랄 데 마체르 니클레에르
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    • C—CHEMISTRY; METALLURGY
    • C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22F—CHANGING THE PHYSICAL STRUCTURE OF NON-FERROUS METALS AND NON-FERROUS ALLOYS
    • C22F1/00—Changing the physical structure of non-ferrous metals or alloys by heat treatment or by hot or cold working
    • C22F1/16—Changing the physical structure of non-ferrous metals or alloys by heat treatment or by hot or cold working of other metals or alloys based thereon
    • C22F1/18—High-melting or refractory metals or alloys based thereon
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02—Fuel elements
    • G21C3/04—Constructional details
    • G21C3/06—Casings; Jackets
    • G21C3/07—Casings; Jackets characterised by their material, e.g. alloys
    • C—CHEMISTRY; METALLURGY
    • C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22C—ALLOYS
    • C22C16/00—Alloys based on zirconium
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Abstract

수냉각 및 감속 원자로용 핵연료봉 클래딩은 지르칼로이 4의 내부층과 지르코늄 및 불가피한 불순물 이외에, 중량으로 주석 0.35%-0.65%$, 철 0.18%-0.25%, 크롬 0.07%-0.13%, 및 산소 0.19%-0.23%(철, 크롬, 주석, 및 산소 함유량의 합계는 1.26% 이하임)를 함유한 지르코늄-기재 합금의 외부분으로 이루어진다. 별도로 또는 추가로 나오븀 0.80%-1.20중량%로 이루어지며 그후 산호 함량은 0.10%-0.16중량%이다. 외부층의 두께는 클래딩의 총두께의 10%-25%이다, 변형으로, 철 크롬, 니오븀, 0.5%까지의 동일량의 바나듐으로 대체된다.Fuel rod cladding for water-cooled and decelerated reactors is 0.35% -0.65% $, 0.18% -0.25% iron, 0.07% -0.13% chromium, and 0.19 oxygen by weight, in addition to the inner layer of zircaloy 4 and zirconium and unavoidable impurities. The outer part of the zirconium-based alloy containing% -0.23% (the sum of iron, chromium, tin, and oxygen content is 1.26% or less). Separately or additionally it consists of 0.80% -1.20% by weight of naobium followed by a coral content of 0.10% -0.16% by weight. The thickness of the outer layer is 10% -25% of the total thickness of the cladding, which is replaced by iron chromium, niobium, the same amount of vanadium up to 0.5%.

Description

핵연료봉 및 이러한 연료봉의 클래딩 제조방법Nuclear fuel rods and cladding manufacturing method of such fuel rods

본 내용은 요부공개 건이므로 전문내용을 수록하지 않았음Since this is an open matter, no full text was included.

Claims (10)

중량으로 주석 1.20%-1.70%, 철 0.18%-0.24%, 크롬 0.07%-0.13%(철과 크롬 함량의 합계는 0.28%-0.37%임)를 함유한. 지르코늄-기재합금의 내부층;및 지르코늄 및 불가피한 불순물 이외에, 중량으로 주석 0.35%-0.65%, 철 0.18%-0.25%, 크롬 0.07%-0.13%, 및 산소 0.19%-0.23%(철, 크롬 주석 및 산소 함량의 합계가 1.26중량%이하임), 및/또는 니오븀 0.80%-1.20중량%(그후 산소 함량이 0.10%-0.16중량%임)를 함유한 지르코늄-기재 합금의 외부층이 있고, 외부층의 두께가 클래딩의 총두께의 10%-25%인, 클래딩에 밀폐된 연료 펠릿으로 이루어진, 수냉각 및 감속 원자로용 연료봉.By weight 1.20% -1.70% tin, 0.18% -0.24% iron, 0.07% -0.13% chromium (the sum of iron and chromium content is 0.28% -0.37%). Inner layers of zirconium-based alloys; and 0.35% -0.65% tin, 0.18% -0.25% iron, 0.07% -0.13% iron, and 0.19% -0.23% oxygen (iron, chromium tin) in addition to zirconium and unavoidable impurities And an outer layer of zirconium-based alloy containing a total of oxygen content less than or equal to 1.26% by weight), and / or 0.80% to 1.20% by weight of niobium, which is then 0.10% to 0.16% by weight of oxygen. A fuel rod for water cooling and deceleration reactors, consisting of fuel pellets enclosed in the cladding, wherein the layer thickness is 10% -25% of the total thickness of the cladding. 중량으로 주석 1.20%-1.70%, 철 0.18%-0.24%, 크롬 0.07%-0.13%(철과 크롬 함량의 합계는 0.28%-0.37%임)를 함유한. 지르코늄-기재합금의 내부층이 있고, 지르코늄 및 불가피한 불순물 이외에, 중량으로 주석 0.35%-0.65%, 철 0.18%-0.25%, 크롬 0.07%-0.13%, 및 산소 0.19%-0.23%, 실리콘 200ppm까지 (철, 크롬 주석 및 산소 함량의 합계가 1.26중량%이하임)함유한 지르코늄-기재 합금의 외부층이 있는, 스트레스가 제거된 클래딩에 밀폐된 연료 펠릿으로 이루어진, 수냉각및 감속 원자로용 연료봉.By weight 1.20% -1.70% tin, 0.18% -0.24% iron, 0.07% -0.13% chromium (the sum of iron and chromium content is 0.28% -0.37%). There is an inner layer of zirconium-based alloy, in addition to zirconium and unavoidable impurities, by weight 0.35% -0.65%, iron 0.18% -0.25%, chromium 0.07% -0.13%, and oxygen 0.19% -0.23%, silicon up to 200 ppm A fuel rod for water-cooled and decelerated reactors, consisting of fuel pellets enclosed in a stress-free cladding with an outer layer of zirconium-based alloys containing (total iron, chromium tin, and oxygen content up to 1.26% by weight). 중량으로 주석 1.20%-1.70%, 철 0.18%-0.24%, 크롬 0.07%-0.13%(철과 크롬 함량의 합계는 0.28%-0.37%임)를 함유한. 지르코늄-기재합금의 내부층이 있고, 지르코늄 및 불가피한 불순물이외에, 중량으로 니오븀 0.80%-1.20%및 산소 0.10%-0.16%를 함유한 지르코늄-기재합금의 외부층이 있는 재경정화 클래딩에 밀폐된 연료 펠릿으로 이루어진, 수냉각 및 감속 원자로용 연료봉.By weight 1.20% -1.70% tin, 0.18% -0.24% iron, 0.07% -0.13% chromium (the sum of iron and chromium content is 0.28% -0.37%). Fuel enclosed in a re-hardening cladding with an inner layer of zirconium-based alloy and with an outer layer of zirconium-based alloy containing 0.80% -1.20% niobium and 0.10% -0.16% oxygen in addition to zirconium and unavoidable impurities Fuel rods for water cooled and decelerated reactors, consisting of pellets. 제2항에 있어서, 외부층 함량이 Fe 또는 Cr의 0.05%까지의 양이 동일량의 바나듐으로 대체되는 것이 특징인 연료봉.3. The fuel rod of claim 2, wherein the outer layer content is replaced by an equal amount of vanadium in an amount up to 0.05% of Fe or Cr. 중량으로 주석 1.20%-1.70%, 철 0.18%-0.24%, 크롬 0.07%-0.13%(철과 크롬 함량의 합계는 0.28%-0.37%임)를 함유한. 지르칼로이 4의 내부층이 있고, 지르코늄 및 불가피한 불순물 이외에, 중량으로 주석 0.35%-0.65%, 철 0.18%-0.25%, 크롬 0.07%-0.13%, 및 산소 0.19%-0.23%, 실리콘 200ppm까지 (철, 크롬 주석 및 산소 함량의 합계가 1.26중량%이하임)함유한 지르코늄-기재 합금의 외부층이 있는 핵연료 부재용 클래딩의 제조방법으로서, 지르칼로이 4의 내부층과 지르코늄-기재 합금으로 구성된 외부 블랭크가 있는 복합체 빌릿을 말단 용접에 의해 형성하고; 그 내부층과 외부 블랭크를 접합하기 위해 약 650℃에서 빌릿을 압축하여 듀플렉스 튜브 블랭크를 형성하며; 이와 같이 얻어진 듀플렉스 튜브 블랭크를 일련의 열-가공 사이클에 의해 변형시킨다음;클래딩을 열적으로 스트레스-제거하는 최종 단계를 수행하는 것으로 이루어진 핵연료 부재용 클래딩의 제조방법.By weight 1.20% -1.70% tin, 0.18% -0.24% iron, 0.07% -0.13% chromium (the sum of iron and chromium content is 0.28% -0.37%). There is an inner layer of Zircaloy 4, in addition to zirconium and unavoidable impurities, by weight 0.35% -0.65%, iron 0.18% -0.25%, chromium 0.07% -0.13%, and oxygen 0.19% -0.23%, up to 200 ppm of silicon ( A method of producing a cladding for a nuclear fuel element with an outer layer of zirconium-based alloys containing a total of iron, chromium tin and oxygen content of 1.26% by weight or less, comprising an inner layer of zircaloy 4 and an outer layer of zirconium-based alloys Blank composite billets are formed by end welding; Compressing the billet at about 650 ° C. to bond the inner layer and the outer blank to form a duplex tube blank; The duplex tube blanks thus obtained are deformed by a series of heat-processing cycles; a method of producing a cladding for a fuel member, comprising performing a final step of thermally stress-removing the cladding. 제5항에 있어서, 최종 아닐링을 약 485℃에서 수행하는 것이 특징인 제조방법.The method of claim 5, wherein the final annealing is performed at about 485 ° C. 7. 제5항에 있어서, 사이클이 약 735℃와 700℃에서 연속 아닐링시키는 것으로 이루어진 것이 특징인 제조방법.The method of claim 5, wherein the cycle consists in continuous annealing at about 735 ° C. and 700 ° C. 7. 지르칼로이 4의 내부층과 지르코늄-니오븀-산소 합금으로 구성된 외부 블랭크를 포함한 복합체 빌릿을 말단 용접에 의해 제공하고;약 650℃에서 그 빌릿을 압출하며; 이와 같이 얻어진 듀플렉스-튜브 블랭크를 압연단계 사이에 중간 재결정화 열처리로 이루어진 일련의 열금속 사이클에 의해 변형시킨다음;최종 재결정화 단계를 수행하는 것으로 이루어진, 제5항에 따른 연료봉 클래딩의 제조방법.Providing, by end welding, a composite billet comprising an inner layer of zircaloy 4 and an outer blank composed of a zirconium-niobium-oxygen alloy; extruding the billet at about 650 ° C .; A duplex-tube blank thus obtained is deformed by a series of hot metal cycles consisting of an intermediate recrystallization heat treatment between rolling steps; a method of producing a fuel rod cladding according to claim 5, comprising performing a final recrystallization step. 제8항에 있어서, 최종 재결정화 열처리를 약 580℃에서 수행하는 것이 특징인 제조방법.The method of claim 8, wherein the final recrystallization heat treatment is performed at about 580 ° C. 10. 제8항에 있어서, 중간 재결정화 열처리를 약 582℃와 700℃에서 수행하는 것이 특징인 제조방법.The method of claim 8, wherein the intermediate recrystallization heat treatment is performed at about 582 ° C. and 700 ° C. 10. ※ 참고사항 : 최초출원 내용에 의하여 공개하는 것임.※ Note: The disclosure is based on the initial application.
KR1019930000501A 1992-01-17 1993-01-15 Nuclear fuel rods and cladding manufacturing method of such fuel rods KR930017045A (en)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
FR9200486A FR2686445B1 (en) 1992-01-17 1992-01-17 NUCLEAR FUEL PENCIL AND METHOD FOR MANUFACTURING THE SHEATH OF SUCH A PENCIL.
FR9200486 1992-01-17

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ES (1) ES2092240T3 (en)
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CZ2193A3 (en) 1993-09-15
ES2092240T3 (en) 1996-11-16
SK17393A3 (en) 1993-09-09
EP0552098B1 (en) 1996-09-11
FI930181A (en) 1993-07-18
HU9300113D0 (en) 1993-04-28
FI930181A0 (en) 1993-01-15
FR2686445A1 (en) 1993-07-23
JPH06194473A (en) 1994-07-15
US5373541A (en) 1994-12-13
HUT64431A (en) 1993-12-28
DE69304555D1 (en) 1996-10-17
EP0552098A1 (en) 1993-07-21
ZA93265B (en) 1994-07-15
CZ281896B6 (en) 1997-03-12
FR2686445B1 (en) 1994-04-08
DE69304555T2 (en) 1997-02-27

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